Experimental determination of the fission-neutron fluence-to-dose conversion factor

Elmaghraby, Elsayed K.; Abdelaal, Saad; Abdelhady, A.M.; Fares, S.; Salama, S.; Mansour, Nabil

doi:10.1016/j.nima.2019.162889

Cited by 11 publications

(3 citation statements)

References 42 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…However, there is a simple experimental remark in neutron physics: whenever the neutron energy distribution repudiates the proper thermalization distribution (Maxwellian+1/E dependence in the epi-thermal region) by any mean such as absorption, the neutrons rapidly redistribute their velocity population within the diffusion distance to follow the proper distribution-up to thermalization. [2,71,72]. To compensate for such dependence, in the present work we introduced a parameterized factor to enhance the formula in equation (42) in the epi-thermal range as follows: which, also, satisfies the condition in equation (13).…”

Section: Probability Of the Neutron Interactionmentioning

confidence: 99%

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

Elmaghraby,

Mahmoud,

Salama

et al. 2024

Phys. Scr.

View full text Add to dashboard Cite

In the current study, an ab initio derivation of the neutron self-shielding factor to solve the complex neutron transport problem of the decrease of the neutron ﬂux as it penetrates into a material placed in an isotropic neutron ﬁeld. The theory of steady-state neutron transport was employed, starting from Stuart’s formula, to derive simple analytical formulae based on the integral cross-section parameters. The formulae could be adopted by the user according to various variables, such as the neutron ﬂux distribution and geometry of the simulation at hand. The concluded formulae of the self-shielding factors comprise an inverted sigmoid function normalized with a weight representing the ratio between the macroscopic total and scattering cross-sections of the medium. The general convex volume geometries are reduced to a set of chord lengths, while the neutron interaction probabilities within the volume are parameterized to the epithermal and thermal neutron energies. The arguments of the inverted-sigmoid function were derived from a simpliﬁed version of neutron transport formulation. The derived analytic formulae agreed greatly with the experimental observations for diﬀerent elements and geometries.

show abstract

Section: Probability Of the Neutron Interactionmentioning

confidence: 99%

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

Elmaghraby,

Mahmoud,

Salama

et al. 2024

Phys. Scr.

View full text Add to dashboard Cite

show abstract

“…However, there is a simple experimental remark in neutron physics: whenever the neutron energy distribution repudiate the proper thermalization distribution (Maxwellian+1/E dependance in epi-thermal region) by any mean such as absorption, the neutrons rapidly redistribute its velocity population within the diffusion distance to follow the proper distribution -up to thermalization. [2,51,52]. To compensate such dependence, in the present work we had introduced a parameterized factor to enhance formula in Eq.…”

Section: Probability Of the Neutron Interactionmentioning

confidence: 99%

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

W.¹,

Elmaghraby²,

Salama³

et al. 2022

Preprint

Self Cite

View full text Add to dashboard Cite

The complexity of the neutron transport phenomenon throws its shadows on every physical system wherever neutron is produced or used. In the current study, an ab initio derivation of the neutron self-shielding factor, the problem of the decrease of the neutron flux as it penetrates into a material placed in an isotropic neutron field, has been attempted employing the theory of steady-state neutron transport, starting from Stuart's formula. Simple formulae were derived based on the integral cross-section parameters, which can be adopted by the user according to various variables, such as the neutron flux distribution and geometry of the simulation at hand. The concluded formulae of the self-shielding factors comprise an inverted sigmoid function normalized a weight representing the ratio between the total and scattering macroscopic cross-sections of the medium. The general convex volume geometries are reduced to a set of chord lengths, while the neutron interactions probabilities within the volume are parameterized to the epithermal and thermal neutron energies. The arguments of the inverted-sigmoid function were derived from a simplified version of neutron transport formulation. Accordingly, the obtained general formulae were successful in giving the experimental values of the neutron self-shielding factor for different elements and different geometries. The results were validated by comparing them to the experimental data as well as a variety of data extracted from the literature.

show abstract

“…Radiation isn't used as much as it used to be because it can change the molecular weight or break down some major parts. For example, polymers, hydrogels, and packaging materials that are exposed to up to 10 KGy of gamma irradiation can have their molecular weight change slightly or break down [8,9]. Chemical dosimeters are materials that were manufactured from radiation-sensitive compounds.…”

Section: Introductionmentioning

confidence: 99%

The effect of gamma-irradiation on absorption spectrum of fluorescein dye

Abdullah

Abul-Hail

Badran

2023

Basrah Researches Sciences

View full text Add to dashboard Cite

In this study, the fluorescein dye was dissolved in the solvent Dimethyl Form amide (DMF). Weighed equivalent to 0.0664, 0.0996 and 0.132 gm from the material. Using 5mM of solvent, each weight of the substance was dissolved separately to obtain the concentration 60 and 80 mM respectively. The effects of both concentration and gamma radiation on optical spectrum of all samples were investigated at room temperature. After irradiation and within the different concentration percentage at fix dose (4.7 KGy), where the results showed increase absorbance with increase concentration (40, 60 and 80 mM). Also, it is found that the decrease absorbance spectrums at wavelength 460 and 487 nm with increase dose and the good stability absorbance spectrum with time. Because of this, the structures in question are regarded as an efficient material for carrying out real-time gamma radiation dosimetry at ambient temperature.

show abstract

Experimental determination of the fission-neutron fluence-to-dose conversion factor

Cited by 11 publications

References 42 publications

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

The effect of gamma-irradiation on absorption spectrum of fluorescein dye

Contact Info

Product

Resources

About